Profile SFR-52 SWAT JAPAN. Japan Atomic Energy Agency, 4002 Narita, Oarai-machi, Ibaraki, Japan.

Transcription

1 Profile SFR-52 SWAT JAPAN GENERAL INFORMATION NAME OF THE FACILITY ACRONYM COOLANT(S) OF THE FACILITY LOCATION (address): OPERATOR CONTACT PERSON (name, address, institute, function, telephone, ): SWAT Sodium-WAter reaction Test facility Sodium Oarai Research and Development Center, Japan Atomic Energy Agency, 4002 Narita, Oarai-machi, Ibaraki, Japan. JAEA Hidemasa YAMANO Advanced Fast Reactor Cycle System Research and Development Center, Sector of Fast Reactor Research and Development Japan Atomic Energy Agency 4002 Narita, Oarai-machi, Ibaraki, , Japan Tel , STATUS OF THE In operation FACILITY Start of operation (date): TS #1 (SWAT-1R): 1999, TS #2 (SWAT-3R): 2001 MAIN RESEARCH FIELD(S) Zero power facility for V&V and licensing purposes Design Basis Accidents (DBA) and Design Extended Conditions (DEC) Thermal-hydraulics Coolant chemistry Materials Systems and components Instrumentation & ISI&R TECHNICAL DESCRIPTION Description of the facility SWAT-1R and SWAT-3R are test facilities to evaluate the tube failure/pressure propagation caused by water leak from heat transfer tube in steam generator (SG) of sodium-cooled fast reactor. These facilities simulate the secondary cooling system and reaction product release

2 system in real plant, and consist of sodium system, water/steam system, release system and gas supply system, and so on. The purification system is installed in SWAT-3R. SWAT-1R possesses 745 kg of sodium and reaction vessel (simulated SG) of 0.5 m inside diameter, 4.3 m in height. Basic data for sodium-water reaction phenomena such as temperature distribution in reaction jet, wastage of tubes, heat transfer coefficient between reaction jet and tube can be acquired by using SWAT-1R. Each system in SWAT-1R is shown in the following. Sodium system consists of reaction vessel (RV), dump tank, piping and valves, etc. Test section is fabricated to fit the test objectives and installed in RV. Water/steam system consists of water heater (WH), piping and valves, etc. Water/steam required in sodium-water reaction test is lead into RV. Release system consists of reaction product storage tank (RT), hydrogen gas discharge piping, reaction product drainage piping and valves, etc. Reaction products due to sodium-water reaction are separated by liquid (sodium compound) and hydrogen gas in RT, hydrogen gas is discharged to the atmosphere while burning. Gas supply system consists of argon/nitrogen gas cylinders, connecting piping and vales, etc. Argon and nitrogen gas are supplied to sodium system and water/steam system respectively. SWAT-3R possesses 15tons of sodium and reaction vessel (simulated SG) of 1.3m inside diameter, 7.7m in height. Synthesis validation data such as tube failure propagation are obtained under from intermediate to large water leak rate conditions. Each system and component in SWAT-3R are shown in the following. Sodium main circulation system consists of reaction vessel, electromagnetic pump, sodium tank, sodium heater, piping and valves, etc. Test section is fabricated to fit the test objectives and installed in RV. Sodium purification system consists of cold trap, economizer, plugging meter, piping and valves, etc. Reaction product can be removed in cold trap, and purity of sodium can be elevated. Heat is exchanged by the temperature difference between inlet and outlet of cold trap. Sodium charge/drain system consists of dump tank (DT), piping and valves, etc. DT serves as the pathway of release system at the time of sodium-water reaction test, reaction products are separated crudely in DT. Gas supply system consists of argon/nitrogen gas cylinders, vapour trap, vacuum pump, air compressor, piping and valves, etc. Reaction product release system consists of reaction product storage tank (RT), hydrogen gas discharge piping, reaction product drainage piping and valves, etc. Rupture disc is burst and pressure in RV is maintained lower. Reaction products due to sodium-water reaction are separated by liquid (sodium compound) and hydrogen gas in RT, hydrogen gas is discharged to the atmosphere while burning. Water/steam system is classified roughly into two systems and consists of water heater, water feeding header, steam catch tank, piping and valves. One system is used for water/steam injection as initial leak, the other is used to cool inside adjacent tubes. Sodium cleaning device is used for stabilization treatment of sodium which attached to a structure due to humid carbon dioxide.

3 In SWAT tests, test section fabricated to fit test objectives is mounted into RV. And sodium system is vacuumed and is substituted for argon gas. In test operation, sodium system is heated and sodium in DT is transferred to sodium system. Then sodium and water/steam system are elevated up to test conditions (equivalent to operation conditions of real SG plant). After test condition is regulated, injection valve is opened and high temperature and high pressure water/steam is lead into RV. Sodium-water reaction data are measured synchronously by data logger at a sampling rate of 50 ms. Acceptance of radioactive material No

4 Scheme/diagram FIG. 1. Flow diagram of Small-scale Sodium-water reaction test rig (SWAT-1R)

5 FIG. 2. Flow diagram of Large-scale Sodium-water reaction test facility (SWAT-3R)

6 3D drawing/photo SWAT-1R FIG. 3. Sodium system of SWAT-1R FIG. 4. Test section (inner structure of RV) of SWAT-1R

7 SWAT-3R FIG. 5. Full view of SWAT-3R test facility FIG. 6. Test section (inner structure of RV) of SWAT-3R

8 Parameters table Coolant inventory Power Test sections TS #1 (SWAT-1R) TS #2 (SWAT-3R) Coolant chemistry measurement and control (active or not, measured parameters) Instrumentation TS #1: 745 kg of sodium TS #2: 15 ton of sodium TS #1: 200 kw TS #2: 1,200 kw (1.2 MW) Characteristic dimensions (Reaction vessel (simulated SG)) TS #1: Inner diameter 0.5 m, Height 4.3 m TS #2: Inner diameter 1.3 m, Height 7.7 m Static/dynamic experiment Dynamic Temperature range in the test section (Delta T) Maximum temperature: About 1200 C (About the difference of 700 K) Operating pressure and design pressure TS #1: Operating Pressure 0.1 MPa (gauge), Design Pressure 1.96 MPa(gauge) in sodium side, Operating Pressure MPa (gauge), Design Pressure MPa(gauge) in water side TS #2: Operating Pressure 0.1 MPa (gauge), Design Pressure 1.96 MPa(gauge) in sodium side, Operating Pressure 19.6 MPa (gauge), Design Pressure 24 MPa(gauge) in water side Flow range (mass, velocity, etc.) TS #1: Stagnant (Sodium) TS #2: 2.3 m 3 /min (sodium) None. Thermocouples, Pressure transducers, Electromagnetic flow meter, Differential pressure type flowmeter, Void sensors, Level gauge, Acoustic sensors, Rupture discs. COMPLETED EXPERIMENTAL CAMPAIGNS: MAIN RESULTS AND ACHIEVEMENTS In SWAT-1R, a first campaign (three tests) was carried out to confirm the thermal influence of target tube due to reacting jet under water leak rate of g/s. The surface temperature of target tubes were estimated by metallographic observation, temperature distribution of reaction jet and heat transfer coefficients between jet and tube were measured. A second campaign (two tests) was carried out to clarify the effect of cover-gas pressure on temperature distribution of reaction jet. Maximum temperature was increasing with pressure enhancement. It was confirmed that the size of reaction jet at higher pressure was smaller than that at lower pressure. A third campaign (12 tests) was carried out to confirm the target wastage rate of 12Cr-1Mo steel. It was confirmed that the wastage rate for 12Cr-1Mo steel is the same as that for stainless steel (SUS304). A forth campaign was carried out to confirm the

9 heat transfer coefficient (HTC) between reaction jet and target tube under JSFR SG operation condition. It was confirmed that HTC under JSFR SG condition is a little bigger than that for Monju condition, the maximum of HTC was limited by average value plus 2 or 3*sigma (standard deviation). In SWAT-3R, a first campaign (three tests) was carried out to confirm the wastage environment around target tube under intermediate water leak condition of 1 kg/s for JSFR SG. The surface temperature on wastage tube was estimated by metallographic observation, it was confirmed that wastage rate and surface temperature in case of superheat steam injection was higher than those in case of saturated steam. A second campaign (three tests) was carried out to confirm the tube failure propagation behaviour in straight tube type SG. Temperature distribution, heat-affected temperature of tube and failure time were measured in a partially simulated tube bundle of large scale SG. PLANNED EXPERIMENTS (including time schedule) No experimental program is planned in 2014 and TRAINING ACTIVITIES Training activities have been carried out before the operation of experimental campaign based on a quality management system of JAEA. REFERENCES (specification of availability and language) 1. NISHIMURA M., SHIMOYAMA K., KURIHARA A., SEINO H., Sodium-water reaction test to confirm thermal influence on heat transfer tubes, JNC-TN (Japanese) 2. FUTAGAMI S., KURIHARA A., YATABE T., Thermal-Hydraulic Characteristics of Sodium-Water Reaction Jet - Effect of Cover Gas Pressure on Temperature Distribution -, JNC-TN (Japanese) 3. SHIMOYAMA K., Wastage-Resistant Characteristics of 12Cr Steel Tube Material - Small Leak Sodium-Water Reaction Test-, JNC-TN (Japanese) 4. KURIHARA, S., KIKUCHI, R. UMEDA, H. OHSHIMA, THE EFFECT OF FLOW-ACCELERATED CORROSION WITH HIGH-TEMPERATURE SODIUM HYDROXIDE ON TUBE TARGET-WASTAGE CAUSED IN STEAM GENERATOR OF SODIUM-COOLED FAST REACTOR, JOURNAL OF JAPAN SOCIETY OF MECHANICAL ENGINEERS-B, VOL. 79, NO. 799, 2013, PP (Japanese) 5. KURIHARA, R. UMEDA, K. SHIMOYAMA, Y. ABE, KIKUCHI S., OHSHIMA H., Heat Transfer Characteristics of Sodium-Water Reaction Jet around a Tube in Steam Generator of Sodium-Cooled Fast Reactor, Journal of Japan Society of Mechanical Engineers-B, Vol. 79, No. 808, 2013, pp (Japanese)

10 6. KIKUCHI S., OHSHIMA H. et al, "Theoretical Study of Sodium-Water Surface Reaction Mechanism," Journal of Power and Energy Systems, Vol.6, No.2 (2012). (En) 7. KIKUCHI S., SEINO H., KURIHARA A, OHSHIMA H., "Kinetic Study of Sodium- Water Surface Reaction by Differential Thermal Analysis," Journal of Power and Energy Systems, Vol.7, No.2 (2013). (En)